SASSYS validation with the EBR-II shutdown heat removal tests

Conference · Sat Dec 31 23:00:00 EST 1988

OSTI ID:5496892

Herzog, J P ^[1]

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1. Argonne National Lab., IL (USA)

SASSYS is a coupled neutronic and thermal hydraulic code developed for the analysis of transients in liquid metal cooled reactors (LMRs). The code is especially suited for evaluating of normal reactor transients -- protected (design basis) and unprotected (anticipated transient without scram) transients. Because SASSYS is heavily used in support of the IFR concept and of innovative LMR designs, such as PRISM, a strong validation base for the code must exist. Part of the validation process for SASSYS is analysis of experiments performed on operating reactors, such as the metal fueled Experimental Breeder Reactor -- II (EBR-II). During the course of a series of historic whole-plant experiments, EBR-II illustrated key safety features of metal fueled LMRs. These experiments, the Shutdown Heat Removal Tests (SHRT), culminated in unprotected loss of flow and loss of heat sink transients from full power and flow. Analysis of these and earlier SHRT experiments constitutes a vital part of SASSYS validation, because it facilitates scrutiny of specific SASSYS models and of integrated code capability. 12 refs., 11 figs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5496892
• Report Number(s): CONF-891140-3; ON: DE90001924
• Country of Publication: United States
• Language: English

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99 GENERAL AND MISCELLANEOUS
990220 -- Computers
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& Computer Programs-- (1987-1989)
ACCIDENTS
BLACKOUTS
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CODES
COOLING SYSTEMS
DATA ANALYSIS
DESIGN
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FEEDBACK
FLUID FLOW
FLUID MECHANICS
GEOMETRY
HEAT TRANSFER
HYDRAULICS
LICENSING
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MATHEMATICS
MECHANICS
POWER GENERATION
POWER REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR LICENSING
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SCRAM
SHUTDOWN
SODIUM COOLED REACTORS
TEMPERATURE EFFECTS
TESTING
TRANSIENTS